Normalized Performance

Slides:

Advertisements

Similar presentations

Frame design Status TB-SWG May 2005 Presented by K. Ioki Prepared by M. Morimoto VV and Blanket Division, ITER Garching ITER.

Advertisements

Design Study of Fusion DEMO Plant at JAERI Japan Atomic Energy Research Institute K. Tobita, S. Nishio, M. Enoeda, M. Sato, T. Isono, S. Sakurai, H. Nakamura,S.

ASIPP Zhongwei Wang for CFETR Design Team Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies February 26-28, 2013 at Kyoto University.

PhD studies report: "FUSION energy: basic principles, equipment and materials" Birutė Bobrovaitė; Supervisor dr. Liudas Pranevičius.

Conceptual design of a demonstration reactor for electric power generation Y. Asaoka 1), R. Hiwatari 1), K. Okano 1), Y. Ogawa 2), H. Ise 3), Y. Nomoto.

A Roadmap to the realization of fusion energy Francesco Romanelli European Fusion Development Agreement EFDA Leader and JET Leader 17 May 2013 Acknoledgments:

Introduction condition of a tokamak fusion power plant as an advanced technology in world energy scenario ○ R.Hiwatari, K.Tokimatsu, Y.Asaoka, K.Okano,

Physics of fusion power Lecture 14: Anomalous transport / ITER.

2010 US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies at UCSD CA, US, Feb.23-24, Commissioning scenario including divertor.

Development Scenario of Tokamak Reactor for Early Demonstration of Electric Power Generation US/Japan Workshop on Power Plant Studies and Related Advanced.

IPP Stellarator Reactor perspective T. Andreeva, C.D. Beidler, E. Harmeyer, F. Herrnegger, Yu. Igitkhanov J. Kisslinger, H. Wobig O U T L I N E Helias.

Japan considerations on design and qualification of PFC's for near term machines (ITER) Satoshi Suzuki 1, Satoshi Konishi 2 1 Japan Atomic Energy Agency.

DEMO Parameters – Preliminary Considerations David Ward Culham Science Centre This work was jointly funded by the EPSRC and by EURATOM.

EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT C L O S E S U P P O R T U N I T G A R C H I N G page 1 of 31 Overview of Reactor Studies in Europe David Maisonnier.

The main function of the divertor is minimizing the helium and impurity content in the plasma as well as exhausting part of the plasma thermal power. The.

ARIES Systems Studies: ARIES-I and ARIES-AT type operating points C. Kessel Princeton Plasma Physics Laboratory ARIES Project Meeting, San Diego, December.

Y. ASAOKA, R. HIWATARI and K

Indian Fusion Test Reactor

India’s Strategy for Fusion Energy R. Srinivasan Institute for Plasma Research, Bhat, Gandhinagar – , India.

Power Extraction Research Using a Full Fusion Nuclear Environment G. L. Yoder, Jr. Y. K. M. Peng Oak Ridge National Laboratory Oak Ridge, TN Presentation.

Y. Sakamoto JAEA Japan-US Workshop on Fusion Power Plants and Related Technologies with participations from China and Korea February 26-28, 2013 at Kyoto.

Prof. F.Troyon“JET: A major scientific contribution...”25th JET Anniversary 20 May 2004 JET: A major scientific contribution to the conception and design.

Early Realization of Fusion Electricity Target and Path by Kunihiko OKANO Central Research Institute of Electric Power Industry (CRIEPI)

Case Study of Roadmap to Tokamak Demo Reactor in Japan International Workshop MFE Roadmapping in the ITER Era September 7, 2011 Princeton, New Jersey,

Norbert Holtkamp, October Status of the ITER Project Norbert Holtkamp Status of the ITER Project Norbert Holtkamp Principal Deputy Director General.

Status and Prospects of Nuclear Fusion Using Magnetic Confinement Hartmut Zohm Max-Planck-Institut für Plasmaphysik, Garching, Germany Invited Talk given.

Power Plant Conceptual Studies in Europe

Selection of Plasma Facing Components for ITER and ITER Operational plan V. Chuyanov (Thanks to Y. Shimomura ) ITPA Garching May

Overview of the KSTAR commissioning M. Kwon 3 June, 2008.

EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT 16th TOFE Madison, Sept , EUROPEAN TECHNOLOGICAL EFFORT IN PREPARATION OF ITER CONSTRUCTION ROBERTO.

Divertor Design Considerations for CFETR

Programmatic issues to be studied in advance for the DEMO planning Date: February 2013 Place:Uji-campus, Kyoto Univ. Shinzaburo MATSUDA Kyoto Univ.

KIT Objectives in Fusion by 2020 Workshop on the European Fusion Roadmap for FP8 and beyond April 13 – 14, 2011; IPP Garching.

University of Texas Confidential, Patents pending Fusion Driver (CFNS) NSTX - Super U and CFNS M. Kotschenreuther, S. Mahajan, P.Valanju Institute for.

European Fusion Power Plant Conceptual Study - Parameters For Near-term and Advanced Models David Ward Culham Science Centre (Presented by Ian Cook) This.

JT-60U -1- Access to High  p (advanced inductive) and Reversed Shear (steady state) plasmas in JT-60U S. Ide for the JT-60 Team Japan Atomic Energy Agency.

US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies February 23-24, 2010 at USCD in USA Platform on integrated design of fusion.

Improved performance in long-pulse ELMy H-mode plasmas with internal transport barrier in JT-60U N. Oyama, A. Isayama, T. Suzuki, Y. Koide, H. Takenaga,

1 EAST Recent Progress on Long Pulse Divertor Operation in EAST H.Y. Guo, J. Li, G.-N. Luo Z.W. Wu, X. Gao, S. Zhu and the EAST Team 19 th PSI Conference.

NSTX XP818: ELM mitigation w/midplane coils – SAS, JKP, RM, SG XP818: Exploratory approach to finding ELM mitigation solution with midplane non-axisymmetric.

Electric Field Lines Contents: Basic Concept Field Lines and point charges Field Lines and conductors.

TFE 3/2/2004 – Fuel retention in JET - J. Bucalossi / T. Loarer Assessment of fuel retention in JET : Contingency – 2 shifts on 6 th of february E. Tsitrone.

The tritium breeding blanket in Tokamak fusion reactors T. Onjun1), S. Sangaroon2), J. Prasongkit3), A. Wisitsorasak4), R. Picha5), J. Promping5) 1) Thammasat.

Study on Plasma Startup Scenario of Helical DEMO reactor FFHR-d1

DEMO Concept Development and Assessment of Relevant Technologies

Numerical investigation of H-mode threshold power by using LH transition models 8th Meeting of the ITPA Confinement Database & Modeling Topical Group.

DCLL TBM Reference Design

X.R. Wang, M. S. Tillack, S. Malang, F. Najmabadi and the ARIES Team

8th Meeting of the ITPA Confinement Database & Modeling Topical Group

Higher ne and Te by ECH pre-ionization in a Trapped Particle Configuration (TPC), a mirror like configuration that enables trapping of particle by magnetic.

Design Concept of K-DEMO for Near-Term Implementation

11th IAEA Technical Meeting on H-mode Physics and Transport Barriers" , September, 2007 Tsukuba International Congress Center "EPOCHAL Tsukuba",

The European Power Plant Conceptual Study Overview

High Temperature Blanket and Its Socio-Economic Issues

Heat flux width scaling in ITER limiter configurations

N. Asakura, K. Shimizu, K. Tobita Japan Atomic Energy Agency, Naka

Comments on ARIES-ACT 10/20/2010 Pre-Strawman

Martin Peng, ORNL FNST Meeting August 18-20, 2009

Integrated Operation of Steady-state Long Pulse H-mode in EAST

The Engineering Challenges of ITER Norbert Holtkamp PDDG Nominee October 16th, 2006 Norbert Holtkamp, October 2006.

Update of ARIES ACT-1 systems analysis

Systems analysis of ACT2 design space

Summary slide for Conceptual Design Study for Heat Exhaust Management in the ARC Fusion Pilot Plant, E.A. Tolman et al., IAEA- FIP-P1-22 Introduction ARC,

A. Vertkov et al., SC “Red Star”, Moscow, Russia

First “Full-Physics” Reactor Simulations Show Potential of Advanced Tokamak as Basis for a Compact-AT Pilot Plant Park/Buttery FIP P3/26 (“CAT”) FASTRAN.

Theoretical Model of ITER High Resolution H-alpha Spectroscopy for a Strong Divertor Stray Light and Validation Against JET-ILW Experiments.

TCV Heating and In-vessel Upgrades for Addressing DEMO Physics Issues

Modelling of pulsed and steady-state DEMO scenarios G. Giruzzi et al

Modelling of Transitions Between L- and H-Mode

ACT-1 design point definition

Presentation transcript:

Normalized Performance Key Concept of JA DEMO FIP/3-2, Y. Sakamoto Operational flexibility from pulse to Steady state Pfus ~ 1.5 GW (Pgross~ 0.5 GWe) for Steady state Pfus ~ 1.0 GW (Pgross~ 0.3 GWe) for 2hrs pulse with moderate plasma performance for commissioning Parameter Steady state 2hrs pulse Size & Configuration Rp (m) 8.5  ap (m) 2.42 A 3.5 k95 1.65 q95 4.1 Ip (MA) 12.3 BT (T) 5.94 BTmax (T) 12.1 Absolute Performance Pfus (MW) 1462 1085 Pnet (MWe) 303 185 Q 17.5 13 PADD (MW) 83.7 83.5 ne (1019m-3) 6.6 6.5 Normalized Performance HH98y2 1.31 1.13 bN 3.4 2.6 fBS 0.61 0.46 fCD 0.39 0.32 ne/nGW 1.2 Feasible DEMO based on ITER technologies. Blanket: ITER-TBM strategy in Japan Divertor: Water cooling and W mono-block divertor Magnet: Radial Plate structure, CIC conductor (Nb3Sn)